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Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Latest News
U.K.’s NWS gets input from young people on geological disposal
Nuclear Waste Services, the radioactive waste management subsidiary of the United Kingdom’s Nuclear Decommissioning Authority, has reported on its inaugural year of the National Youth Forum on Geological Disposal forum. NWS set up the initiative, in partnership with the environmental consultancy firm ARUP and the not-for-profit organization The Young Foundation, to give young people the chance to share their views on the government’s plans to develop a geological disposal facility (GDF) for the safe, secure, and long-term disposal of radioactive waste.
Wei-Wu Chao, Jay F. Kunze, Weimin Dai, Sudarshan K. Loyalka
Nuclear Technology | Volume 105 | Number 2 | February 1994 | Pages 261-270
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT94-A34927
Articles are hosted by Taylor and Francis Online.
Research reactors present a different set of operating conditions than do light water (power) reactors (LWRs). Thermal-hydraulic transient/safety codes, such as the Reactor Loss of Coolant Analysis Program (RELAP), have been verified against experimental data from several test facilities designed for the operating conditions of LWRs. However, the operating pressures, temperatures, fuel type, and flow direction are quite different in most high-power research reactors. Furthermore, the coolant (water) in these reactors generally is not degasified and hence contains dissolved air. Results are given of benchmark experiments compared with RELAP predictions for the conditions encountered during a loss-of-coolant accident for a typical research reactor.